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R.A. Bennett
Observed names:
R Bennett,
R. A. Bennett,
R. BENNETT,
R. Bennett
Institution:
Idaho National Laboratory
Observed institutions:
Battelle,
General Electric (United States),
Idaho National Laboratory,
United States Atomic Energy Commission
OpenAlex ID:
A5022891963
Determination of k∞ from Critical Experiments with the PCTR
1958
·
D. J. Donahue
, D. D. Lanning
, et al.
·
Nuclear Science and Engineering
·
18
Neutron Rethermalization Cross Section Measurements in Graphite
1960
·
R. A. Bennett
, R. E. Heineman
·
Nuclear Science and Engineering
·
9
Reactivity worth of gas expansion modules (GEMs) in the Fast Flux Test Facility
1986
·
L.R. Campbell
, J.V. Nelson
, et al.
·
Transactions of the American Nuclear Society
·
6
Biases for current FFTF calculational methods
1978
·
P.A. Ombrellaro
, R.A. Bennett
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
4
Neutron Rethermalization in Graphite and Water
1963
·
R. A. Bennett
·
Nuclear Science and Engineering
·
4
Initial Fuel Load and Criticality, Zero Power and Characterization Testing
1980
·
R.A. Bennett
, D. H. Jones
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
2
PDF
Initial Physics Measurements on FFTF
1980
·
R.A. Bennett
, J.W. Daughtry
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
2
PDF
Buffalo light water reactor calculations
1979
·
P.A. Ombrellaro
, R.A. Bennett
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
2
FFTF reactor characterization program
1977
·
J.W. Daughtry
, R.A. Bennett
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
2
PDF
Investigation of Modelling Methods for Ftr Burnup Calculations.
1972
·
Hanford Engineering Development Lab., Richland, Wash.
, J. Nelson
, et al.
·
2
PDF
Rationale and Plans for the FTR Critical Experiments Program
1967
·
R. Bennett
, P. Hofmann
·
2
The Absorption Cross Section of Copper for Thermal Neutrons
1960
·
D. J. Donahue
, R. A. Bennett
, et al.
·
Nuclear Science and Engineering
·
2
Multifrequency Binary Sequence Testing at the Fast Flux Test Facility
1989
·
R. A. Harris
, Yau Ming Chien
, et al.
·
Nuclear Science and Engineering
·
1
FFTF reactor characterization program review
1982
·
J.A. Rawlins
, F.S. Moore
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
1
Evaluation of MSM for assessing subcritical reactivities in FFTF
1980
·
P.A. Ombrellaro
, R.A. Harris
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
1
Neutron environmental characterization requirements for reactor fuels and materials development and surveillance programs
1975
·
W.N. McElroy
, R.A. Bennett
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
1
Analysis of Ftr Control-rod Experiments Performed in Zpr-3 Assembly 48 and 48a.
1967
·
Sven Engström
, R.A. Bennett
·
Transactions of the American Nuclear Society
·
1
Fast Flux Test Reactor: Critical Experiments Program.
1966
·
R.A. Bennett
, P. Hofmann
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
1
Open-cycle gas core reactor research and development at INEL
1991
·
C. MOTLOCH
, R. BENNETT
, et al.
·
Conference on Advanced SEI Technologies
Fast Flux Test Facility fuel and test management: The first 10 years
1991
·
R.A. Bennett
, C. L. Bennett
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Reactor physics results from fast flux test facility operation
1990
·
R.A. Harris
, L.R. Campbell
, et al.
·
Transactions of the American Nuclear Society
FFTF operational results
1982
·
C.L. Peckinpaugh
, R.A. Bennett
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
USA/FBR program fast flux test facility startup physics and reactor characterization methods and results
1981
·
R.A. Bennett
, R.A. Harris
, et al.
·
University of North Texas Digital Library (University of North Texas)
PDF
Measurement and calculation of neutron spectra in the FTR engineering mockup critical
1977
·
J.V. Nelson
, E.P. Lippincott
, et al.
PDF
Status of safety-related FFTF neutronics parameters
1976
·
R.A. Bennett
, J.W. Daughtry
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
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Works count:
45
Citation count:
61
H-index:
4
I10-index:
1
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